ML16336A532

7 to Updated Final Safety Analysis Report, Chapter 3, Table 3.4.1-1

ML16336A532
Person / Time
Site:	Cook
Issue date:	10/24/2016
From:	Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML16336A263	List: AEP-NRC-2016-42, Fire Protection Program Change Summary ML16336A225 ML16336A228 ML16336A238 ML16336A291 ML16336A292 ML16336A294 ML16336A295 ML16336A297 ML16336A298 ML16336A299 ML16336A300 ML16336A301 ML16336A302 ML16336A303 ML16336A304 ML16336A305 ML16336A306 ML16336A308 ML16336A309 ML16336A310 ML16336A311 ML16336A312 ML16336A313 ML16336A314 ML16336A315 ML16336A316 ML16336A317 ML16336A318 ML16336A319 ML16336A320 ML16336A322 ML16336A323 ML16336A324 ML16336A325 ML16336A327 ML16336A328 ML16336A329 ML16336A330 ML16336A332 ML16336A333 ML16336A334 ML16336A336 ML16336A337 ML16336A338 ML16336A339 ML16336A340 ML16336A341 ML16336A342 ML16336A345 ... further results
References
AEP-NRC-2016-42
Download: ML16336A532 (2)

Text

INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 24.0 Table:

3.4.1-1 Page:

1 of 2 UNIT 1 THERMAL AND HYDRAULIC DESIGN PARAMETERS Cycle 1 Design Parameters1 Total Heat Output, MWt 3250 Total Heat Output, Btu/hr 11,090 x 106 Heat Generated in Fuel, %

97.4 Maximum Thermal Overpower, %

112 Nominal System Pressure, psia 2250 Hot Channel Factors Heat Flux Nuclear, Fq 2.60 Engineering, E

qF 1.03 Total 2.80 Enthalpy Rise Nuclear N

F 1.55 Coolant Flow Total Flow Rate, lbs/hr 135.6 x 106 Average Velocity along Fuel Rods, ft/sec 15.5 Average Mass Velocity, lb/hr-ft2 2.53 x 106 Coolant Temperature, °F Design Nominal Inlet 536.32 Average Rise in Vessel 63.0 Average Rise in Core 65.7 Average in Core 570.3 Average in Vessel 567.8 Nominal Outlet of Hot Channel 667.5 Heat Transfer Active Heat Transfer Surface Area, ft2 52,200 Average Heat Flux, Btu/hr-ft2 207,000 Maximum Heat Flux, Btu/hr-ft2 579,600 Maximum Thermal Output, kw/ft 18.8 Maximum Clad Surface Temperature BOL at Nominal Pressure, °F 657 Maximum Average Clad Temperature BOL at Rated Power, °F 720 1 See Table 3.5.3-1 for current cycle design parameters.

2 Best Estimate Nominal Inlet Temperature is 533.0 °F

INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision: 24.0 Table:

3.4.1-1 Page:

2 of 2 UNIT 1 THERMAL AND HYDRAULIC DESIGN PARAMETERS Fuel Central Temperatures (Region 3-BOL) or nominal fuel rod dimensions, °F Maximum at 100% Power 4250 Maximum at 112% Power 4500 Design Parameters DNB Ratio Minimum DNB Ratio at nominal operating conditions 1.97 Pressure Drop, psi Across Core 32 Across Vessel, including nozzles 51